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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Application of Adjoint Based Node Optimization Method to MARS Jae Jun Lee, Min-Gil Kim, Seongmin Son, and Jeong Ik Lee(KAIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Coupling of FLUENT and ANLHTP for Steady-state Thermal Analysis of a Heat Pipe Cooled Reactor Core San Lee and Hyoung Kyu Cho(SNU), Changho Lee and Taek K. Kim(ANL) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Preliminary Study of the Artificial Neural Networks to Replace the Constitutive Equations in the Reactor Safety Analysis Code ChoHwan Oh, Sung Gil Shin, Seongmin Son, Doh Hyeon Kim, and Jeong Ik Lee(KAIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Preliminary Calculation of SGTR with HPSI Failure in OPR1000 using SPACE Code Dong-ha Lee, Yeon-sik Cho, and Jae-seung Suh(SENTECH) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Sensitivity Analysis of Reflood Model with RBHT Experiment Wonwoong Lee and Jeong Ik Lee(KAIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Preliminary Study on Modified Steam Turbine Modeling of the MARS-KS Code Doh Hyeon Kim, Jae Jun Lee, Jeong Yeol Baek, Yonghee Kim, and Jeong Ik Lee(KAIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Thermal-Hydraulic Analysis of MSGTR Event in OPR1000 using SPACE Code Jae-ho Bae, Yeon-sik Cho, and Jae-seung Suh(SENTECH) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Preliminary Study of Correlation between Variables in Sensitivity Analysis of PWR Safety Analysis Min-Gil Kim and Jeong Ik Lee(KAIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Preliminary Multi-Physics Analysis of OPR1000 Reactor Core using Coupled CUPID and nTER Youyeon Choi and Hyoung Kyu Cho(SNU), Jin Young Cho(KAERI) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Design Study of Heat Pipes for Nuclear Spaceship Applications Ye Yeong Park, YeongShin Jeong, and In Cheol Bang(UNIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Flow Characteristics of Molten Salt Natural Circulation in Non-uniform Heat Flux Condition using Open FOAM Dong Hun Lee, Seok Bin Seo, Yeong Shin Jeong, and In Cheol Bang(UNIST) PDF보기 -
2019-Spring 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.23(Thu) 13:00 로비 (3F) Thermal Hydraulic Analysis of TES Integrated PWR Cycle Ju Yeon Lee and Jeong Ik Lee(KAIST) PDF보기 -
2019-Spring 6A : 원자력 안전 (Nuclear Safety) 5.23(Thu) 09:00 202B (2F) Simulator-based Time Reliability Curve for HRA of Digitalized Main Control Room Wondea Jung(KAERI), Eun-chan Lee(KHNP CRI) PDF보기 -
2019-Spring 6A : 원자력 안전 (Nuclear Safety) 5.23(Thu) 09:20 202B (2F) Application of a PSA Tool for Accident Sequence Precursor Evaluation Chang-Ju Lee and Dongju Jang(KINS), Sang Hoon Han(KAERI) PDF보기 -
2019-Spring 6A : 원자력 안전 (Nuclear Safety) 5.23(Thu) 09:40 202B (2F) A Preliminary Site Risk Assessment for Multi-unit Nuclear Power Plants Wonjong Song, Seunghyun Jang, Dohyun Lim, Yein Seo, Sunghyun Park, and Moosung Jae(HYU) PDF보기 -
Last Modified : 1998-Autumn